Investigation of reactivity changes due to flooding the irradiation sites of the MNSR reactor using the MCNP code and comparison with experimental results

In this work, the Isfahan Miniature Neutron Source Reactor (MNSR ) has been simulated using the MCNP code, and reactivity worth of flooding the inner irradiation sites of this reactor in an accident has been calculated. Also, by inserting polyethylene capsules containing water inside the inner irrad...

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Bibliographic Details
Main Authors: A Shirani, h Shamoradi, I Shahabi
Format: Article
Language:English
Published: Isfahan University of Technology 2010-06-01
Series:Iranian Journal of Physics Research
Subjects:
Online Access:http://ijpr.iut.ac.ir/browse.php?a_code=A-10-1-451&slc_lang=en&sid=1